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4$$times$$4バンドルにおける気液二相流ボイド率分布の計測

Measurement of void fraction distribution in two-phase flow in a 4$$times$$4 bundle

Liu, W.; 永武 拓; Jiao, L.; 柴田 光彦; 小松 正夫*; 高瀬 和之; 吉田 啓之 

Liu, W.; Nagatake, Taku; Jiao, L.; Shibata, Mitsuhiko; Komatsu, Masao*; Takase, Kazuyuki; Yoshida, Hiroyuki

原子力機構では、事故時を対象とした炉心内二相流解析の予測精度の向上等を目的として、ワイヤーメッシュセンサーを用い、高温高圧条件(2MPa, 212$$^{circ}$$C)下でのバンドル内ボイド率データの取得を行っている。試験装置は、9$$times$$9ワイヤーメッシュセンサーを4$$times$$4の模擬バンドル内に、軸方向2カ所に配置したものである。本報では、空気-水二相流に対して、大気圧室温条件で実施した試験により得た、試験装置及び計測システムの妥当性確認結果や、炉心スクラム後を想定した低流量条件でのバンドル内ボイド率分布計測結果について報告する。

To improve and validate the prediction accuracy of two - phase codes, Japan Atomic Energy Agency is working on the measurement of void faction distribution in rod bundles with using wire mesh sensors, under high pressure and high temperature conditions (2MPa, 212$$^{circ}$$C). The test section is a 4$$times$$4 rod bundle, in which two three - layer 9$$times$$9 wire mesh sensors are installed at two different axial positions. As the first step of the experiment, to validate the measuring system, we performed experiments in water - air system under atmospheric pressure, with using water and air flow rates as parameters. Void fraction distributions in the sub-channels of the rod bundle were derived in a wide flow pattern from bubbly flow to slug flow. The water flow rate, from the viewpoint of considering the natural circulation after reactor scrum, was lower than 600 kg/m$$^{2}$$s. The data will be used to validate the void fraction correlations and two-phase evaluation codes.

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